References
- D. WACHS, “Transient Testing of Nuclear Fuels and Materials in the United States,” JOM, 64, 1396 (2012); https://doi.org/10.1007/s11837-012-0482-2.
- N. WOOLSTENHULME et al., “Development of Irradiation Test Devices for Transient Testing,” Nucl. Technol., 205, 1251 (2019); https://doi.org/10.1080/00295450.2019.1590072.
- D. KAMERMAN et al., “Transient Testing of Uranium Silicide Fuel in Zircaloy and Silicon Carbide Cladding,” Ann. Nucl. Energy, 160, 108410 (2021); https://doi.org/10.1016/j.anucene.2021.108410.
- J. SCHULTHESS et al., “Post-Transient Examination of Performance of Uranium Silicide Fuel and Silicon-Carbide Composite Cladding Under Reactivity-Initiated Accident Conditions,” J. Nucl. Mater., 560, 153520 (2022); https://doi.org/10.1016/j.jnucmat.2022.153520.
- C. FOLSOM et al., “Overview of the Water Based RIA Testing in TREAT,” presented at the TOPFUEL2021 Conf., Santander, Spain, October 24–28, 2021.
- J. SCHULTHESS et al., “Non-destructive Post-Irradiation Examination Results of the First Modern Fueled Experiments in TREAT,” J. Nucl. Mater., 541, 152442 (2020); https://doi.org/10.1016/j.jnucmat.2020.152442.
- J. SCHULTHESS et al., “Post-Transient Examination of Reactivity-Initiated Accident Tested Uranium Silicide Fuel and Silicon-Carbide Composite Cladding,” presented at the TOPFUEL2021 Conf., Santander, Spain, October 24–28, 2021.
- B. SPENCER et al., “Dry In-Pile Fracture Test (DRIFT) for Separate-Effects Validation of Ceramic Fuel Fracture Models,” J. Nucl. Mater., 568, 153816 (2022); https://doi.org/10.1016/j.jnucmat.2022.153816.
- L. SENIS et al., “Evaluation of Gamma-Ray Transmission Through Rectangular Collimator Slits for Application in Nuclear Fuel Spectrometry,” Nucl. Instrum. Methods Phys. Res. Sect. A, 1014, 165698 (2021); https://doi.org/10.1016/j.nima.2021.165698.
- N. CAPPS et al., “A Critical Review of High Burnup Fuel Fragmentation, Relocation, and Dispersal Under Loss-of-Coolant Accident Conditions,” J. Nucl. Mater., 546, 152750 (2021); https://doi.org/10.1016/j.jnucmat.2020.152750.
- W. WIESENACK, “Summary of the Halden Reactor Project LOCA Test Series IFA-650,” HPR-380, Institute for Energy Technology (IFE) - Organization for Economic Co-operation and Development (OECD) Halden Reactor Project (2013).
- W. WIESENACK, “Summary and Comparison of LOCA Tests with BWR Fuel in the Halden Reactor Project Test Series IFA-650,” Institutt for Energiteknikk, Halden, Norway (2015).
- H. SONNENBURG et al., “Report on Fuel Fragmentation, Relocation, and Dispersal,” Nuclear Energy Agency/Committee on Safety of Nuclear Installations (2016).
- M. BALES et al., “Interpretation of Research on Fuel Fragmentation, Relocation, and Dispersal at High Burnup,” U.S. NRC RIL 2021-13, U.S. Nuclear Regulatory Commission, Office of Nuclear Regulatory Research (2021); https://adamswebsearch2.nrc.gov/webSearch2/main.jsp?AccessionNumber=ML21309A013 (current as of Feb. 9, 2022).
- B. A. COOK et al., “Reactivity Initiated Accident Test Series Test RIA 1-2 Fuel Behavior Report,” NUREG/CR-1842 EGG-2073, Idaho National Engineering Laboratory (1981).
- C. HELSENGREEN, “Instrumentation and Re-fabrication Techniques Used for Fuel Rod Performance Characterization in the Halden Reactor,” IAEA-TECDOC-CD-1635, International Atomic Energy Agency (2009); https://www.osti.gov/etdeweb/biblio/21433466 (current as of Feb. 9, 2022).
- H. J. KLEEMAN and B. C. OBERLAENDER, “Re-fabrication and Instrumentation−Resume and Outlook,” NEI-NO-1472, Norway (2005); https://www.osti.gov/etdeweb/biblio/20599365 (current as of Feb. 9, 2022).
- OECD HALDEN REACTOR PROJECT, “Thermal Performance of High Burn-Up LWR Fuel,” Seminar Proc., Cadarache, France, March 3–6, 1998; https://www.oecd-nea.org/upload/docs/application/pdf/2019-12/1247-thermal-cadarache-1998.pdf#page=74 (current as of Feb. 9, 2022).
- K. SILBERSTEIN, “Refabricated and Instrumented Fuel Rods,” HOTLAB Plenary Mtg., Halden Norway, September 6–8, 2004; https://inis.iaea.org/collection/NCLCollectionStore/_Public/36/058/36058887.pdf?r=1 (current as of Feb. 9. 2022).
- C. JENSEN et al., “Post-Halden Reactor Irradiation Testing for ATF: Preliminary Assessment and Recommendations,” INL/EXT-18-46101, Idaho National Laboratory (2018); https://inldigitallibrary.inl.gov/sites/sti/sti/Sort_6087.pdf (current as of Feb. 9, 2022).
- J. SCHULTHESS et al., “FY21 Progress Report for Advanced Re-fabrication/Re-instrumentation Capability Development,” INL/EXT-21-64543, Idaho National Laboratory (2021); https://inldigitallibrary.inl.gov/sites/sti/sti/Sort_53102.pdf (current as of Feb. 9, 2022).
- F. CAPPIA, “Non-destructive Examinations of ATF-2 Baseline Rods,” INL/EXT-20-58495, Idaho National Laboratory (2020); https://inldigitallibrary.inl.gov/sites/sti/sti/Sort_24843.pdf (current as of Feb. 9, 2022).
- K. A. TERRANI et al., “Young’s Modulus Evaluation of High Burnup Structure UO2 with Nanometer Resolution,” J. Nucl. Mater., 508, 33 (2018); https://doi.org/10.1016/j.jnucmat.2018.04.004.
- D. T. HAGRMAN, C. M. ALLISON, and G. A. BERNA, “SCDAP/RELAP5/MOD 3.1 Code Manual: MATPRO, A Library of Materials Properties for Light-Water-Reactor Accident Analysis,” NUREG/CR-6150-Vol. 4; EGG-2720-Vol. 4, U.S. Nuclear Regulatory Commission (1995).
- J. SPINO et al., “Matrix Swelling Rate and Cavity Volume Balance of UO2 Fuels at High Burn-Up,” J. Nucl. Mater., 346, 2–3, 131 (2005); https://doi.org/10.1016/j.jnucmat.2005.06.015.